Heat Transfer for a Nuclear Reactor Review Heat Transfer PowerPoint PPT Presentation

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Title: Heat Transfer for a Nuclear Reactor Review Heat Transfer


1
Heat Transfer for a Nuclear Reactor
2
Review Heat Transfer Terms
  • Conduction-occurs across the medium
  • 1
  • Convection-occurs between a surface and a moving
    fluid
  • 2
  • Radiation Heat Transfer-occurs between two
    surfaces
  • 3

3
Subjects
  • Heat generation
  • Decay heat
  • Transfer in the elements
  • Plate
  • Cylinder
  • Transfer to the Coolant
  • Coolant channels
  • Other coolants
  • Boiling Regimes
  • Design Criteria
  • Loss of Coolant Accident (LOCA)

4
Heat Generation
  • 200 MeV/ fission (ER)
  • Ed Energy deposited in locally 180MeV
  • Number of fissions in a core are a function of
    the FLUX(f)
  • FLUX is a function of position in the core f(r,z)

5
Heat Generation
r
z
H
R
6
Decay heat
  • Heat is released as the accumulated fission
    products decay
  • The amount of heat is ? fission products ? to the
    power level

7
Coolant Flow qw(hout-hin)
Recirculating
Steam Tout
Tout
q
q
Tin
WaterTin
8
Plate fuel
ab
T(x)
a
a ab
X
9
Cylinder
TF
z
Tc
Ts
a
Tmax
ab
10
Transfer to the coolant
  • For a Cylinder bltlta

Off the surface
coolant
fuel
11
Coolant Channels
  • Now you need to remember more heat transfer and
    fluid mechanics
  • The heat transfer for a channel is

12
Other coolants
  • Gas cooled Helium
  • Pebble bed in development
  • Liquid sodium and potassium
  • Need corrosive resistant structure

13
Boiling Heat Transfer
Annular flow
Bulk boiling
Bubbly flow
T
Local boiling
ln q
14
The Boiling Crisis
Full film
T
Partial film
Annular flow
ln q
15
LOCA
  • Address component breakdown or a combination of
    component breakdowns that lead to interruption of
    normal cooling
  • When an interruption occurs, the fission process
    is terminated, however heat generation continues

16
Classifications of operation
  • Normal
  • Operational transients
  • Upsets
  • Emergencies
  • Limiting Fault Conditions includes Design basis
    accident DBA
  • Unprotected or beyond DBA

17
Engineered Safety Systems
  • The actions are done as a result of instrument
    signals
  • Reliability
  • Duplication
  • Diversity

18
Most common ESS
  • Alternate cooling
  • SCRAM - Tripping - insert control rods to stop
    fission
  • Control
  • Cool
  • Contain

19
Some examples
  • Millstone 1(660 MWe BWR) - corrosion of
    condensers leads to sea water to enter primary
    cooling circuit
  • Browns ferry fire -(2 1065 MWe BWR 1 in
    construction) fire affected 2000 cables cause
    about 10 M
  • Three mile island- relief valve stuck open
  • Ginna 490 MWe PWR- rupture in a steam generator
    tube
  • Mihama-2 - 500 MWe PWR rupture in a steam
    generator tube

20
More examples
  • Chornobyl-Chernobyl
  • Chalk River - NRX- control rod/ operator error
    forerunner to the CANDU
  • Windscale fire- UK large air cooled pile designed
    for Pu burst fuel cartridge
  • St. Laurent - French
  • Hunterston scotland - Seawater in the reactor
    vessel
  • Hinckley point
  • EBR-1 and Fermi -1 fast breeder.
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